ANS / Publications / Journals / Nuclear Science and Engineering

An Unequal Velocity Model for Transient Two-Phase Flow by the Method of Characteristics

Dimitri Gidaspow, Firooz Rasouli, Yong W. Shin

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 179-195

Technical Paper / dx.doi.org/10.13182/NSE83-A17788

Modeling Film Boiling Destabilization Due to a Pressure Shock Arrival

Michael L. Corradini

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 196-205

Technical Paper / dx.doi.org/10.13182/NSE83-A17789

Generalized Perturbation Theory with Derivative Operators for Power Density Investigations in Nuclear Reactors

L. A. Belblidia, J. M. Kallfelz, D. G. Cacuci

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 206-225

Technical Paper / dx.doi.org/10.13182/NSE83-A17790

Fast Neutron Spectra by Integral Experiments on Graphite with a Collimated Monoenergetic (D, T) Neutron Beam

A. Tsechanski, M. Segev, G. Shani

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 226-233

Technical Paper / dx.doi.org/10.13182/NSE83-A17791

Neutron Capture Resonances in ⁵⁶Fe and ⁵⁸Fe in the Energy Range from 10 to 100 keV

F. Käppeler, K. Wisshak, L. D. Hong

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 234-247

Technical Paper / dx.doi.org/10.13182/NSE83-A17792

Neutron Fission Cross Sections of ²³⁹Pu and ²⁴⁰Pu Relative to ²³⁵U

L. W. Weston, J. H. Todd

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 248-259

Technical Paper / dx.doi.org/10.13182/NSE83-A17793

Streaming of 14-MeV Neutrons Through an Iron Duct—Comparison of Measured Neutron and Gamma-Ray Energy Spectra with Results Calculated Using the Monte Carlo MCNP Code

R. T. Santoro, J. M. Barnes, R. G. Alsmiller, Jr., P. D. Soran

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 260-270

Technical Paper / dx.doi.org/10.13182/NSE83-A17794

Validity of the Monte Carlo Method for Shielding Analysis of a Spent-Fuel Shipping Cask: Comparison with Experiment

K. Ueki, M. Inoue, Y. Maki

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 271-284

Technical Paper / dx.doi.org/10.13182/NSE83-A17795

Particle Transport Theory in a Finite Sphere Containing a Spherical-Shell Source

C. E. Siewert, J. R. Thomas, Jr.

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 285-290

Technical Paper / dx.doi.org/10.13182/NSE84-285

Plutonium Diffusion in Advanced Fuels (U,Pu)(C,O) and (U,Pu)(C,N)

M. H. Bradbury, Hj. Matzke

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 291-293

Technical Note / dx.doi.org/10.13182/NSE83-A17797

Additional Remarks on BeH₂ as a Moderator in Minimum Critical Mass Systems

P. K. Job, K. Subba Rao, M. Srinivasan

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 293-298

Technical Note / dx.doi.org/10.13182/NSE83-A17798

Reduction of “Calculational” Uncertainties Due to Approximate Fission-Source Matrices

U. Salmi, J. J. Wagschal, A. Yaari, Y. Yeivin

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 298-300

Technical Note / dx.doi.org/10.13182/NSE83-A17799

Monte Carlo Calculations of a Fusion Reactor Shielding Experiment

Eldon Schmidt, Philip F. Rose

Nuclear Science and Engineering / Volume 84 / Number 3 / July 1983 / Pages 300-304

Technical Note / dx.doi.org/10.13182/NSE83-A17800